ML20004D083
| ML20004D083 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/01/1981 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 3-051-49, 3-51-49, TAC-08881, TAC-8881, NUDOCS 8106080329 | |
| Download: ML20004D083 (2) | |
Text
{{#Wiki_filter:a ei k f us[ i '. c Florida Power C O A P O m a T *O se I ,g Q/ June 1, 1981
- 3-051-49 rq NJ
-{ JUN O 819815 10 {}1 uMaua,,m,m h'/'/yf@p Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555
SUBJECT:
Crystal River Unit 3 Docket No. 50-302 Facility Operating License No. DPR-72 Snubber Surveillance Technical Specifications
REFERENCES:
NRC Letter to all Licensees dated November 20, 1980 FPC Letter (P. Y. Baynard to D. G. Eisenhut) dated April 3, 1981
Dear Mr. Eisenhut:
As discussed in the letter referenced above, Florida Power Corporation is unaware of any operating experience relevant to our snubbers that woul d indicate a need to increase our snubber surveillance program. Florida Power Corporation representatives participated in the NRC meet-ing on April 13-14, 1981, and will continue to follow operating exper-tence through established channels. We intend to continue to monitor and/or participate in the review process for ANSI /ASME OM-4," Examination and Performance Testing of Nuclear Power Plant Dynamic Restraints (Snub-bers)", and will consider its applicability to Crystal River Unit 3. Florida Power Corporation will also continue the "special studies" on fluid viscosity and potential adverse effects of radiation exposure on hydraulic fluids. Since we lack any basis to do otherwise. Florida Power Corporation re-spectfully declines to submit a technical specification change request at this time. Should your staff wish to pursue this matter further, it is requested that input in the following areas be provided:
- Value/ impact of expanded eurveillance;
- Specific applicab h operating experience indicating need for expanded pro <., ram;
= Specific deficiencies in current program. 8106 080 hM i neral othce 3205 in nriounn weet souen. P O Boa 14042, si Pete'sbu'g honda um. 8 0 8% 5151
Darrell G. Eisenhut Page 2 June 1, 1981 Our current surveillance program, based on earlier revisions of Standard Technical Specifications, is adequate and has proven sufficient to iden-tify any potential problems. It should be noted that Florida Power Cor-poration may, internally, decide to " improve" this or any program over and above Technical Specification requirements should we identify a need to do so. In fact, we are developing more detailed maintenance histor-ies and closer administrative controls over snubber repairs. We urge your consideration of our position and woul d suggest, once again, that a drastic expansion of this program would be ill-advised when both industry standards (ANSI /ASME OM-4) and reguiatory positions (SC-708-4) are in the development stage. Very truly yours, l. Y. Baynard Manager Nuclear Support Services Mardis(R01)D1-3 l i l t .}}